US4752439A - Safety enclosure cooling system for gas cooled high temperature reactors - Google Patents

Safety enclosure cooling system for gas cooled high temperature reactors Download PDF

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Publication number
US4752439A
US4752439A US06/724,959 US72495985A US4752439A US 4752439 A US4752439 A US 4752439A US 72495985 A US72495985 A US 72495985A US 4752439 A US4752439 A US 4752439A
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US
United States
Prior art keywords
concrete
high temperature
gas cooled
cooled high
temperature reactor
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Fee Related
Application number
US06/724,959
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English (en)
Inventor
Claus Elter
Josef Schoening
Winfried Wachholz
Ulrich Weicht
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Hochtemperatur Reaktorbau GmbH
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Hochtemperatur Reaktorbau GmbH
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G21C13/093—Concrete vessels
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention concerns gas cooled high temperature reactors having a cylindrical steel pressure vessel, heat exchanger devices, cooling gas circulation devices and circulating blowers.
  • the state-of-the-art includes installations wherein a high temperature reactor for the nuclear generation of heat and the devices serving the utilization of the heat obtained are installed together in a pressure vessel.
  • the heat is removed by means of a cooling gas which is being circulated with the aid of blowers in a closed loop or primary loop through the reactor core and the heat exchanger devices.
  • special devices such as auxiliary heat exchangers and auxiliary blowers are often provided It is also possible to eliminate these special devices by means of a particular arrangement and layout of the primary loop components.
  • the heat exchangers and the blowers together with the pipe circuits on the secondary side and their components are laid out so that the entire secondary heat is removed by means of the operating systems of the heat exchangers on the primary side
  • the flow of the cooling gas from top to bottom through the reactor core and from bottom to top through the heat exchangers in this case is similar to that in normal operation.
  • the blowers must at all times be ready to function so that the area of the cold gas will not be endangered by the hot gas rising in free convection.
  • the heat exchanger is arranged above the nuclear reactor and the cooling gas flows from bottom to top both through the reactor core and through the heat exchanger.
  • the structures surrounding the reactor core include in addition to a reflector jacket of graphite, a carbon brick enclosure surrounding the graphite jacket and providing shielding and thermal insulation.
  • the aforementioned structures are surrounded by a double, gas-tight steel pressure vessel. A layer of magnetite and limonite between the two steel pressure vessels serves as a biological shield.
  • the function of the biological shield is effected by the prestressed concrete pressure vessel, which houses in a centercavity, the reactor core and the heat exchangers.
  • the prestressed concrete pressure vessel not only serves as the radiation shield, but also provides a complete, pressure resistant containment of the nuclear reactor installation.
  • the present invention is based on a nuclear reactor installation of the type described hereinabove and arranged in a steel pressure vessel. It is an object of the invention to provide such an installation that safely protects the outside and the environment against radiation and the consequences of accidents which may occur within the plant. Another object is to assure the removal of secondary heat in the event of an accident.
  • the nuclear reactor installation is characterized in that the steel pressure vessel is tightly enclosed in a safety enclosure comprising two essentially cylindrical concrete shells in a spaced apart arrangement, a concrete cover monolithically joined with the outer concrete shell and a cantilever ring monolithically joined with both concrete shells and supporting the steel pressure vessel and a concrete cooling system in the innerconcrete shell.
  • the concrete cooling system operates by natural means and comprises cooling water circulating in a closed loop and a second cooling water system to provide for the recooling of the cooling water circulating in the concrete cooling system.
  • the enclosure also functions as a biological shield.
  • the safety enclosure assures the safe containment of the installation against leakage from the primary loop.
  • the safety enclosure thereby forms a containment barrier for the cooling gas in the steel pressure vessel and an additional barrier to retain fission products. (A first barrier to retain fission products is the fuel elements themselves.
  • a nuclear reactor with spherical fuel elements contains the fissionable substance in the form of coated particles.
  • the safety enclosure further protects the nuclear reactor installation against external effects. These effects may consist, for example, of earthquakes, aircraft crashes or pressure waves in the case of explosions.
  • the safety enclosure serves as a supporting structure of the steel pressure vessel.
  • the outer concrete shell has the further function of a protective reactor building, while the inner concrete shell provides protection against debris and fragments.
  • a concrete cooling system is provided within the inner concrete shell.
  • the concrete cooling system removes the heat generated in the concrete by radiation.
  • the heat loss of the steel pressure vessel is also removed by the concrete cooling system. Heat is transferred from the steel pressure vessel primarily by thermal radiation while it is removed from the concrete by direct contact.
  • This concrete cooling system is further used according to the invention for the removal of the secondary heat.
  • the devices normally eliminating the secondary heat are rendered ineffective and the concrete cooling system provides a backup.
  • the devices for the removal of secondary heat consist of the heat exchanger blower units with the operational secondary loop and possibly an auxiliary cooling system. Even in the case of a failure of the blowers, the removal of secondary heat on the primary side may be assured if the cooling gas pressure in the primary circuit is high enough so that natural convection is adequate and may be maintained as such. If, however, the heat sink on the primary side is eliminated, the secondary heat is conducted according to the invention by means of natural convection, conduction and radiation of the steel pressure vessel.
  • the heat is then transferred from the steel pressure vessel essentially by radiation to the concrete cooling system located in the inner concrete shell. Even in the case of the loss of cooling gas (pressure relief incident) and the failure of all cooling in the primary loop, the secondary heat is transferred from the surface of the steel pressure vessel to the concrete cooling system. In this event, no increased release of fission products by the fuel elements is experienced.
  • the concrete cooling system comprises preferably an elevated annular reservoir placed onto the inner concrete shell and maintained under atmospheric pressure, together with ascending pipes and downpipes. Ascending pipes are arranged on the side facing the steel pressure vessel and the downpipes are arranged on the side facing the outer concrete shell of the inner concrete shell.
  • the recooling of the water circulating in the concrete cooling system is effected by a second cooling water system, which removes the heat generated to the elevated reservoir and then to the outside.
  • the water content of the elevated reservoir and the pipe system evaporates at a rate of approximately 2 to 3 t/h.
  • the removal of secondary heat may thereby be assured for several days without any active measures.
  • a device for the continuous supply of water is provided on the elevated reservoir.
  • this device either the removal of the secondary heat may be continued following the evaporation of the concrete cooling system or the concrete cooling system may be operated with a higher heat removal capacity.
  • the inner concrete shell may be equipped with a thickened part directed inwardly.
  • This thickened part is preferably in the form of a flange upon which a supporting ring is resting.
  • the supporting ring is mounted on the jacket of the steel pressure vessel.
  • the supporting ring has the function of securing the steel pressure vessel in case of exposure to an earthquake.
  • the pressure vessel is thereby supported only by the inner concrete shell. Additional support on the outer concrete shell would result in a direct impact of a crashing aircraft on the steel pressure vessel.
  • the safety enclosure in turn may rest on concrete support rings joined monolithically with both concrete shells as well as on the cantilever ring upon which the steel pressure vessel rests.
  • the annular space between the two concrete shells which is accessible to a limited extent during operation, may beused advantageously as a working space.
  • FIG. 1 shows the nuclear reactor installation in a longitudinal cross section, but without the concrete cooling system.
  • FIG. 2 shows a reduced and highly simplified representation of the reactor installation with the concrete cooling system.
  • FIG. 3 shows a high temperature reactor and heat exchangers all housed in a cylindrical steel pressure vessel.
  • FIG. 1 shows a multiple part cylindrical steel pressure vessel 1, the individual parts of which are joined together at the flange 2.
  • a nuclear reactor is installed in the steel pressure vessel 1.
  • the reactor in FIG. 3 comprises a high temperature small reactor 33 located in the lower part of the vessel and having a capacity of 100 MWe, and a heat utilization system arranged in the upper part of the vessel.
  • the heat utilization system comprises a plurality of heat exchange units or generators 34 and circulating blowers 3 following the generators in sequence.
  • the heat exchanger units or generators are conventionally installed.
  • the blowers 3 are mounted laterally on the upper part of the steel pressure vessel 1.
  • the pressure vessel 1 rests on a cantilever ring 4 made of concrete.
  • a safety enclosure 5 is arranged tightly around the steel pressure vessel 1.
  • the enclosure 5 comprises two essentially cylindrical concrete shells, the inner concrete shell 6 and the outer concrete shell 7, together with a concrete cover 9 monolithically joined with the two concrete shells.
  • the cantilever ring 4 is also integrated into the safety enclosure 5.
  • the safety enclosure 5 rests on two support rings 10 and 11 made of concrete. It is again joined monolithically with the rings. Between the two concrete shells 6 and 7, there is an annular space 8, which is accessible to a limited extent and may be used as a work space.
  • passages are provided in the concrete cover 9 and in the center jacket area of the safety enclosures. These passages are closed off with removable pressure resistant and gas-tight covers 12.
  • the passage 13 in the concrete cover 9 permits access to the steam generators in the heat utilization system and makes dismantling of these components also possible.
  • the passages 14 provided in the jacket area of the safety enclosure 5 provide access to the inner concrete shell 6 to the blowers 3.
  • the outer concrete shell 7 into which the covers 12 are set (in FIG. 1 one of the covers 12 has been removed) is reinforced in the area of the passage 14.
  • the circulating blowers 3 may be removed through the passages 14 or maintenance and repair work may be performed on them.
  • the inner concrete shell 6 has thickened part 15 projecting in the inward direction.
  • a ring 16 rests on the part 15. It is set onto the steel pressure vessel 1. The ring 16 secures the steel pressure vessel 1 against earthquakes.
  • passages 17 are provided for a shutdown system 18, which comprises a plurality of absorber rods and their drive devices.
  • a central passage 19 receiving a pebble removal tube 20 is also provided if the small HT reactor is operated with spherical fuel elements.
  • the water supply lines 21 and the live steam lines 22 of the steam generators are installed at the bottom and outside the safety enclosure 5 in the reactor housing 23 surrounding the safety enclosure, passing horizontally through the support ring 11 to the outside.
  • the two concrete shells 6 and 7, together with the annular space 8 have a thickness of approximately 2.70 m. This includes a wall thickness of the inner concrete shell of 0.70 m and a width of 0.80 m of the annular space 8.
  • the safety enclosure 5 has a concrete cooling system 24.
  • This system also has the simultaneous function of removing the secondary heat in case of a failure of the secondary heat removal devices on the primary side in the nuclear reactor installation.
  • the concrete cooling system 24, operated with natural circulation is shown in FIG. 2.
  • the concrete cooling system 24 includes an annular elevated reservoir 25 which is under atmospheric pressure.
  • a plurality of ascending pipes 26 and downpipes 27 form a piping system wherein cooling water circulates in a closed loop.
  • the closed loop is connected with the elevated reservoir 25.
  • the elevated reservoir 25, which contains approximately 100 m 3 water is set onto the inner concrete shell 6. It is connected with a second cooling system 28, wherein cooling water is again circulating. This second cooling water system transfers the heat generated in the elevated reservoir 25 to the outside.
  • the ascending pipes 26 are installed within the inner concrete shell 6 on its side facing the steel pressure vessel 1.
  • the downpipes 27 are on the side facing the outer concrete shell 7.
  • the ascending pipes 26 may be equipped with azimuthal fins or a finned wall (not shown).
  • a blow-off line 29 leading to the outside from the safety enclosure 5 is connected with the elevated reservoir 25.
  • a pressure relief valve 30 is arranged in the blow-off line.
  • the heat is transferred essentially by radiation to the inner concrete shell 6 of the safety enclosure 5.
  • the heat is received by the water rising in the ascending pipes 26 by heat conduction.
  • the heat is transported within the elevated reservoir 25 and thereby transferred to the second cooling water system 28.
  • the water is heated in the elevated reservoir 25, but due to evaporation in reservoir 25 the removal of the secondary heat may be maintained for 2 to 3 days. If it is necessary to provide a longer period of time, the elevated reservoir 25 may also be refilled by means of the inlet line 31.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Pressure Vessels And Lids Thereof (AREA)
  • Driving Mechanisms And Operating Circuits Of Arc-Extinguishing High-Tension Switches (AREA)
  • Electromagnets (AREA)
US06/724,959 1981-10-22 1985-04-22 Safety enclosure cooling system for gas cooled high temperature reactors Expired - Fee Related US4752439A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3141892 1981-10-22
DE3141892A DE3141892C2 (de) 1981-10-22 1981-10-22 Kernreaktoranlage

Related Parent Applications (1)

Application Number Title Priority Date Filing Date
US06425332 Continuation 1982-09-28

Publications (1)

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US4752439A true US4752439A (en) 1988-06-21

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Family Applications (1)

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US (1) US4752439A (ja)
JP (1) JPS5880596A (ja)
DE (1) DE3141892C2 (ja)

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4842810A (en) * 1986-12-12 1989-06-27 Hochtemperatur-Reaktorbau Gmbh Nuclear power plant with a high temperature reactor located eccentrically in a cylindrical prestressed concrete pressure vessel
US4847040A (en) * 1987-01-21 1989-07-11 Hochtemperatur-Reaktorbau Gmbh Nuclear power plant with a gas cooled high temperature reactor
WO1997022974A1 (de) * 1995-12-15 1997-06-26 Siemens Aktiengesellschaft Druckbehälter, insbesondere einer siedewasser-kernkraftanlage
US20030024176A1 (en) * 2001-07-25 2003-02-06 Minoru Kanechika Reactor building of steel concrete construction
US20100177859A1 (en) * 2009-01-08 2010-07-15 Kabushiki Kaisha Toshiba Nuclear reactor building and construction method thereof
US20140321596A1 (en) * 2012-05-21 2014-10-30 Smr Inventec, Llc Passive reactor cooling system
US10665354B2 (en) 2012-05-21 2020-05-26 Smr Inventec, Llc Loss-of-coolant accident reactor cooling system
US11901088B2 (en) 2012-05-04 2024-02-13 Smr Inventec, Llc Method of heating primary coolant outside of primary coolant loop during a reactor startup operation
US11935663B2 (en) 2012-05-21 2024-03-19 Smr Inventec, Llc Control rod drive system for nuclear reactor

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3435255A1 (de) * 1984-09-26 1986-04-03 Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund Kernreaktoranlage mit einem ht-kleinreaktor mit kugelfoermigen brennelementen
DE3446141A1 (de) * 1984-12-18 1986-06-19 Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund In einem stahldruckbehaelter untergebrachte kernreaktoranlage mit einem gasgekuehlten ht-kleinreaktor
DE3534423A1 (de) * 1985-09-27 1987-04-02 Hochtemperatur Reaktorbau Gmbh Kernreaktoranlage mit einem ht-kleinreaktor
AU2001272686A1 (en) * 2000-07-13 2002-01-30 Eskom Nuclear reactor

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US2863815A (en) * 1953-07-23 1958-12-09 Moore Richard Valentine Nuclear reactor
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DE3009390A1 (de) * 1980-03-12 1981-09-17 GHT Gesellschaft für Hochtemperaturreaktor-Technik mbH, 5060 Bergisch Gladbach Hochtemperaturreaktor
US4404165A (en) * 1980-04-15 1983-09-13 Hoechst Aktiengesellschaft Process for carrying away the decay heat of radioactive substances
US4508677A (en) * 1983-02-09 1985-04-02 General Electric Company Modular nuclear reactor for a land-based power plant and method for the fabrication, installation and operation thereof

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US2863815A (en) * 1953-07-23 1958-12-09 Moore Richard Valentine Nuclear reactor
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DE1227160B (de) * 1959-02-24 1966-10-20 Gen Electric Kernreaktoranlage
US3115450A (en) * 1959-02-24 1963-12-24 Gen Electric Nuclear reactor containment apparatus
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US3207671A (en) * 1959-11-24 1965-09-21 Licentia Gmbh Pressure release device to drench reactor core
US3372092A (en) * 1965-03-12 1968-03-05 Atomenergi Ab Nuclear reactor
US3266999A (en) * 1965-03-26 1966-08-16 Richard E Wood Gas-cooled, water moderated neutronic reactor
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US3461034A (en) * 1966-09-06 1969-08-12 Gulf General Atomic Inc Gas-cooled nuclear reactor
US3497421A (en) * 1968-01-15 1970-02-24 Commissariat Energie Atomique Shielded enclosure providing resistance to high temperatures and pressures
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US4061534A (en) * 1969-02-17 1977-12-06 United Kingdom Atomic Energy Authority Nuclear reactors
US3929567A (en) * 1972-04-11 1975-12-30 Siemens Ag Nuclear reactor equipped with a flooding tank and a residual heat removal and emergency cooling system
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DE2623978A1 (de) * 1976-05-28 1977-12-15 Ght Hochtemperaturreak Tech Verfahren und einrichtung zum ableiten im kern eines kernreaktors erzeugter nachzerfallwaerme
DE3009390A1 (de) * 1980-03-12 1981-09-17 GHT Gesellschaft für Hochtemperaturreaktor-Technik mbH, 5060 Bergisch Gladbach Hochtemperaturreaktor
US4404165A (en) * 1980-04-15 1983-09-13 Hoechst Aktiengesellschaft Process for carrying away the decay heat of radioactive substances
US4508677A (en) * 1983-02-09 1985-04-02 General Electric Company Modular nuclear reactor for a land-based power plant and method for the fabrication, installation and operation thereof

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Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4842810A (en) * 1986-12-12 1989-06-27 Hochtemperatur-Reaktorbau Gmbh Nuclear power plant with a high temperature reactor located eccentrically in a cylindrical prestressed concrete pressure vessel
US4847040A (en) * 1987-01-21 1989-07-11 Hochtemperatur-Reaktorbau Gmbh Nuclear power plant with a gas cooled high temperature reactor
WO1997022974A1 (de) * 1995-12-15 1997-06-26 Siemens Aktiengesellschaft Druckbehälter, insbesondere einer siedewasser-kernkraftanlage
US20030024176A1 (en) * 2001-07-25 2003-02-06 Minoru Kanechika Reactor building of steel concrete construction
US20100177859A1 (en) * 2009-01-08 2010-07-15 Kabushiki Kaisha Toshiba Nuclear reactor building and construction method thereof
US8712002B2 (en) * 2009-01-08 2014-04-29 Kabushiki Kaisha Toshiba Nuclear reactor building and construction method thereof
US11901088B2 (en) 2012-05-04 2024-02-13 Smr Inventec, Llc Method of heating primary coolant outside of primary coolant loop during a reactor startup operation
US20140321596A1 (en) * 2012-05-21 2014-10-30 Smr Inventec, Llc Passive reactor cooling system
US9589685B2 (en) * 2012-05-21 2017-03-07 Smr Inventec, Llc Passive reactor cooling system
US10665354B2 (en) 2012-05-21 2020-05-26 Smr Inventec, Llc Loss-of-coolant accident reactor cooling system
US10720249B2 (en) 2012-05-21 2020-07-21 Smr Inventec, Llc Passive reactor cooling system
US11935663B2 (en) 2012-05-21 2024-03-19 Smr Inventec, Llc Control rod drive system for nuclear reactor

Also Published As

Publication number Publication date
DE3141892C2 (de) 1985-10-31
DE3141892A1 (de) 1983-05-11
JPH032276B2 (ja) 1991-01-14
JPS5880596A (ja) 1983-05-14

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